Review of the ITER diagnostics suite for erosion, deposition, dust and tritium measurements

Reichle, R.; Andrew, P.; Bates, Philip K.; Bede, O.; Casal, N.; Choi, Changhwan; Barnsley, R.; Damiani, Carlo; Bertalot, L.; Dubus, Gregory; Ferreol, J.; Jagannathan, G.; Kočan, M.; Leipold, F.; Lisgo, S.; Martin, Vincent; Palmer, J.; Pearce, R.; Philipps, V.; Pitts, R.A.; Pampin, R.; Passedat, G.; Puiu, Adrian; Suárez, Alejandro; Shigin, P.; Shu, W.M.; Vayakis, G.; Veshchev, E.; Walsh, Michael J.

doi:10.1016/j.jnucmat.2015.01.039

Cited by 25 publications

(4 citation statements)

References 9 publications

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“…It is based on the experience of previous LID-QMS measurements [32][33][34]. It will be operational during DTE3 operations in 2023 and will demonstrate the capability for in situ fuel retention analysis including T as foreseen in ITER [10].…”

Section: Design and Operation Of Laser Induced Desorption Diagnosticmentioning

confidence: 99%

“…The data is also used to aid in the design solution and operating schedule of a new laser induced desorption diagnostics to be installed in JET prior to the final deuterium-tritium operations in 2023 (DTE3). This diagnostic will demonstrate the monitoring of fuel retention in plasma facing components within in the fusion vessel, i.e., 'in situ analysis' as foreseen in ITER [10].…”

Section: Introductionmentioning

confidence: 99%

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Evaluation of tritium retention in plasma facing components during JET tritium operations

et al. 2021

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An assessment of the tritium (T) inventory in plasma facing components (PFC) during JET T & DT operations is presented based on the most comprehensive ex-situ fuel retention data set on JET PFCs from the 2015-2016 ILW3 operating period is presented. The global fuel retention is 4.19 x 1023 D atoms, 0.19% of injected fuel. The inner divertor remains the region of highest fuel retention (46.5%). The T inventory in PFCs at the end of JET operations is calculated as 7.48 x 1022 atoms and is informative for accountancy, clean-up efficacy and waste liability assessments. The T accumulation rate at the upper inner divertor during JET deuterium-tritium (DT) operations has been used to assess the requirements and frequency of operation of a new laser induced desorption diagnostic to be installed on JET for the final DT experiments in 2023.

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Section: Design and Operation Of Laser Induced Desorption Diagnosticmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Evaluation of tritium retention in plasma facing components during JET tritium operations

et al. 2021

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“…In search of an on-line backup density measurement for ITER Antoine Sirinelli The retro-reflector in the blanket module has been designed using the interface used by the FW samples diagnostic [3] as shown in Figure 3a. It is a corner-cube inserted in a cylindrical assembly.…”

Section: Pos(ecpd2015)089mentioning

confidence: 99%

Looking For An On-Line Backup Density Measurement For Iter

Sirinelli¹,

Akiyama²,

Orimoto³

et al. 2016

Proceedings of 1st EPS Conference on Plasma Diagnostics — PoS(ECPD2015)

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“…Finally, macroscopic particles penetrating into the confined plasma are a source of high-Z impurities [8] responsible for local plasma cooling, and therefore instabilities, or even disruptions in case of massive inflow [9][10][11]. As a consequence, the total dust content in the vacuum vessel has to be monitored [12] and efficient dust removal methods [13] have to be developed in order to avoid long maintenance periods and the associated operation costs.…”

Section: Introductionmentioning

confidence: 99%

Fast camera observations of injected and intrinsic dust in TEXTOR

Shalpegin

Vignitchouk

Erofeev

et al. 2015

Plasma Phys. Control. Fusion

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Stereoscopic fast camera observations of pre-characterized carbon and tungsten dust injection in TEXTOR are reported, along with the modelling of tungsten particle trajectories with MIGRAINe. Particle tracking analysis of the video data showed significant differences in dust dynamics: while carbon flakes were prone to agglomeration and explosive destruction, spherical tungsten particles followed quasi-inertial trajectories. Although this inertial nature prevented any validation of the force models used in MIGRAINe, comparisons between the experimental and simulated lifetimes provide a direct evidence of dust temperature overestimation in dust dynamics codes. Furthermore, wide-view observations of the TEXTOR interior revealed the main production mechanism of intrinsic carbon dust, as well as the location of probable dust remobilization sites.

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Review of the ITER diagnostics suite for erosion, deposition, dust and tritium measurements

Cited by 25 publications

References 9 publications

Evaluation of tritium retention in plasma facing components during JET tritium operations

Evaluation of tritium retention in plasma facing components during JET tritium operations

Looking For An On-Line Backup Density Measurement For Iter

Fast camera observations of injected and intrinsic dust in TEXTOR

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